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NE 255

Course Title: 
Numerical Simulation in Radiation Transport
Course Units: 
Catalog Description: 
  • Computational methods used to analyze nuclear reactor systems described by various differential, integral, and integro-differential equations. Numerical methods include finite difference, finite elements, discrete ordinates, and Monte Carlo. Examples from neutron and photon transport, heat transfer, and thermal hydraulics. An overview of optimization techniques for solving the resulting discrete equations on vector and parallel computer systems.
Course Prerequisite: 
  • NE 150 or consent of instructor
Topics Covered: 
  • Fundamentals of numerical analysis
  • Computer solutions for 1D eigenvalue problems
  • Iterative computational methods for solving partial differential equations of the elliptic and parabolic type
  • Finite element methods
  • Finite difference method
  • Coarse-mesh rebalancing method
  • Collision probability
  • Monte Carlo methods
Textbook(s) and/or Other Required Materials: 
  • S. Nakamura, "Computational Methods in Engineering and Science," John Wiley & Sons, New York. 1996.
  • Reference Text: E.E. Lewis and W.F. Miller, Jr., "Computational Method of Books: Neutron Transport," John Wiley & Sons, New York. 1984.
  • Reference Text: H. Greenspan, C.N. Kelber and D. Okrent, editors, "Computational Methods in Reactor Physics," Gordon and Breach. 1968.
Class/Laboratory Schedule: 
  • Three hours of lecture per week
Assessment of Student Progress Toward Course Objectives: 
  • Homework: 40%
  • Midterm: 30%
  • Project: 30%